ML19310A439
| ML19310A439 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 06/11/1980 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML19310A436 | List: |
| References | |
| NCR-SQN-CEB-801, NUDOCS 8006170552 | |
| Download: ML19310A439 (1) | |
Text
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a t-ENCLOSURE SEQUOYAH NUCLEAR PLANT UNIT 2 DESIGN CRITERIA FOR SECONDARY SIDE PIPE BREAKS NCR SQN CEB 8012 10 CFR 50.55(e)
FIRST INTERIM REPORT Description of Deficiency Criteria in the Westinghouse steam system's design manc.al, revision 3, for the propagation of secondary side breaks permits a main steam line crack to propagate to another main steam loop if the total flow area from the other steam generator does not exceed three square inches.
This criteria did not provide for the propagation of main steam cracks to other lines such as auxiliary feedwater or steam generator blowdown lines. The present design does not adequately protecc the steam generator blowdown lines inside the west valve room from damage because of a main steam line critical crack.
The auxiliary feedwater lines are being evaluated to determine if they might be similarly affected.
Corrective Action TVA is conducting an evaluation of pipe rupture interaction and protective device requirements for proper protection of the auxiliary feedwater and steam generator blowdown lines. Protective devices will be provided as required.
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